Neutron Transport: Flux and Current

This lecture delves into the complex dynamics of neutron behavior in nuclear reactors, focusing on the evolution of fission products and the practical aspects associated with it. The instructor explains the importance of modeling neutron reactors and the main methods used in the industry. Key concepts covered include neutron fluxes, neutron current, and the neutron balance equation. The lecture also explores the significance of neutron density, angular flux, and scalar flux in predicting power generation and reactor performance. Additionally, the instructor discusses the neutron transport process, emphasizing the distinction between flux and current, and the role of neutron leakage in reactor analysis.